ML18153B555

LER 88-041-00:on 881016,engineering Evaluation Revealed That Existing Lifting Frames Installed Over RHR Pumps,Associated W/Piping & Electrical Supply Lines,Not Seismically Qualified.Caused by Inadequate analysis.W/881114 Ltr

ML18153B555
Person / Time
Site:	Surry
Issue date:	11/15/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-062, 88-62, LER-88-041, LER-88-41, NUDOCS 8811280072
Download: ML18153B555 (4)

Text

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NRC Form 361 U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED 0MB NO. 3161M1104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 TITLE 141 Surry Power Station, Unit 1 &; 2 !o Is I o I o I o 12 1 a I o 1 IOF nI ~

Lifting Frames Over RHR Pumps Not Seismically Qualified EVENT DATE 151 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED (BJ MONTH DAY YEAR FACI L.ITY NAMES DOCKET NUMBER ISi 1 I c 11 s a ala - oI 411 -o Io i Ii ls s Is

______ __ a 1 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or mar* of rha follovying) (111 OPERATING ....._

MODE (91 POWER I O I 01 0 ~

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- OTHER (Spacify in Absrracr 60.3Blcll21 60.73(all211vlll b*low *nd In T*xr, NRC Form 20.405(*111 Jliiil

- 60.731*1121111 60.73(all2JlvlliJIAI 366A) 20.4061*1!1 J(lv) 20.408(*111 IM - 60.73(*11211111 60.73(*112111111 LICENSEE CONTACT FOR THIS LER (121 60.73(all211vlllllBI 60.7311112Jlxl NAME TELEPHONE NUMBER AREA CODE D. L. Benson Station Manaaer 18 . I O I 4 31 r; I 7 I - I ~ 11 I st I u COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT TURER SYSTEM COMPONENT TURER I I I I I I I I I I I I I I I ,I I I I I I !illlllilililililililillliiiiiiil:llliiliiiiiillillli I I I. I I I I SUPPLEMENTAL REPORT EXPECTED l14t MONTH DAY YEAR rx, EXPECTED SUBMISSION

.h YES (If ys1, campier. EXPECTED SUBMISSION DATE) NO DATE 1151 I I I ABSTRACT (Limit to 1400 spac*s. I.*.* *PProxim*mly fifroan singls,spac* ryp*wrlmn lin*s) 1181 On October 16, 1988 with both Units 1 & 2 in Cold Shutdown (CSD) ,. and the Residual Heat Removal (RHR) system in operation, an engineering evaluation revealed that the existing lifting frames installed over the RHR pumps, associated piping, and electrical supply lines, were not seismically qualified. The pumps were declared inoperable, and a* lOCF~S0.72, non-emergency report, was made to the NRC.

It is speculated that the lifting frames were installed as a temporary structure to facilitate maintenance and were never removed. Hence, the appropriate engineering analysis and evaluations were not performed on the structures. As an interim measure, the lifting frames were braced to ensure they would withstand seismic loads. The lifting frames will be removed during the present unit outages and new frames will be designed and installed during future refueling outages.

Present maintenance and engineering practices preclude similar occurrences of placing structures over safety related equipment without adequate engineering reviews.

8811280072 881115 PDR ADOCK 05000280 S PNU NRC Form 318 19-831

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POW 28-06-01 Nhc Farm 366A U.S. NUCLEAR REGULATORY COMMISSIOII!

(9-83)

LICENSEE E .. T REPORT (LER) TEXT CONTINUA. . APPROVED 0MB NO, 3150-0104 EXPIRES: 8/31 /88 F.1!\CIL_riv NAME (1) DOCKET NUMBER (21 PAGE (3)

LER NUMBER (6)

Surry Power Station, Unit 1 & 2 0 1s IO I O IO 12 i 810 Bl 8 .- 0 I4 I1 - 01 0 0 I 2 OF O 13 TEXT (ff more spaca is n,quimd, use additiofllJI NRC Form 366A 'sJ (17) 1.0 Description of the Event On October 16, 1988 with both Units 1 & 2 in Cold Shutdown (CSD), and the Residual Heat Removal (RHR)

{EIIS-BP} system in operation, an engineering evaluation revealed that the existing lifting frames installed over the RHR pumps {EIIS-P}, associated piping, and electrical supply lines, were not seismically qualified. A static .analysis of the frames determined that stresses in excess of the material yield point could exist under seismic loading.

Therefore, since a potential existed for failure of the lifting frames during a design basis earthquake, which could result in the inoperability of the RHR pumps, the pumps were declared inoperable, and a 10CFR50.72, non-emergency report, was made to the NRC.

2.0 Safety Conseguences and Implications The residual heat removal system is required.to bring the re*actor coolant system from conditioi:is' *of approximately 350 degrees Fahrenheit and 450 psig, to cold shutdown conditions. Heat removal at greater temperatures is by the steam and power conversion system. Procedures exist that instruct the operator on actions to take in the event residual heat removal capability is lost. Therefore, the health and safety of the public were not affected.

3.0 Cause Although it is not known when the lifting frames were installed, -it is speculated that they were installeq as a temporary structure to facilitate maintenance and were never removed. Hence, the appropriate engineering analysis and evaluations were not performed on the structures.

4.0 Immediate Corrective Action(s)

As an interim measure, the lifting frames were braced to ensure they would withstand seismic loads.

5.0 Additional Corrective Action(s)

The lifting frames will be removed during the present unit outages. New frames will be designed and install~d during future refueling outages.

NRC FORM 3HA *u.s. GPO, 1988-520-589100070 (9-831

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N~C Form 366A

• LICENSEE E

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T REPORT (LER) TEXT CONTINUA POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31 /88 F"CILITY_NAME' (1) DOCKET NUMBER (21 PAGE 131 LER NUMBER 161 YEAR  ::::::::::: SEQUENTIAL -:,:*:*:*:: REVISION

NUMBER ..... NUMBER Surry Power Station, Unit 1 TEXT (ff more space is n,quimd, use additional NRC Fann 3118A :.J.1171

~ 2 0 I5 I O I O I O I 2 ,s I O 81 8 . . 0 I 4 11 - 0 ~ 0 I 3 OF O I 3 6.0 Action(s) Taken to Prevent Recurrence Pres~nt maintenance and engin~ering practices preclude simi~ar occurrences of placing structures over safety related equipment without adequate engineering reviews.

7.0 Similar Events None.

8.0 Manufacturer/Model Number N/A NRC FORM 31111A *u.s. GPO, 19BB-520-589t00070 (9-831

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e VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P.O. Box 3115 Surry, Virginia 23883

• November 14, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-062 Document Control Desk Docket No.: 50-280 016 Phillips Building 50-281 Washington, D.C. 20555 Licensee No. : DPR-32 DPR-37 Gentlemen:

Pursuant to Surry Power Station Technical* Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Units 1 and 2.

REPORT NUMBER 8~041-00 This report bas been reviewed by the Station Nuclear Safety and Operating C~ttee and will be reviewed by Safety Evaluation and Control.

Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administ~ator Suite 2900 101 Marietta Street, RW Atlanta, Georgia 30323

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